Rao Ankita, Kumar Sharma Abhishek, Kumar Pradeep, Charyulu M M, Tomar B S, Ramakumar K L
Radioanalytical Chemistry Division, Bhabha Atomic Research Centre, Mumbai 400085, India.
Board of Radiation and Isotope Technology, Vashi, Navi Mumbai 400705, India.
Appl Radiat Isot. 2014 Jul;89:186-91. doi: 10.1016/j.apradiso.2014.02.013. Epub 2014 Mar 2.
A new method has been developed for separation and purification of fission (99)Mo from neutron activated uranium-aluminum alloy. Alkali dissolution of the irradiated target (100mg) results in aluminum along with (99)Mo and a few fission products passing into solution, while most of the fission products, activation products and uranium remain undissolved. Subsequent purification steps involve precipitation of aluminum as Al(OH)3, iodine as AgI/AgIO3 and molybdenum as Mo-α-benzoin oxime. Ruthenium is separated by volatilization as RuO4 and final purification of (99)Mo was carried out using anion exchange method. The radiochemical yield of fission (99)Mo was found to be >80% and the purity of the product was in conformity with the international pharmacopoeia standards.
已开发出一种从经中子活化的铀铝合金中分离和纯化裂变（99）Mo的新方法。对辐照靶（100毫克）进行碱溶，铝以及（99）Mo和一些裂变产物进入溶液，而大多数裂变产物、活化产物和铀仍不溶解。后续的纯化步骤包括将铝沉淀为Al(OH)3，将碘沉淀为AgI/AgIO3，将钼沉淀为钼-α-苯偶姻肟。钌以RuO4形式挥发分离，（99）Mo的最终纯化采用阴离子交换法。发现裂变（99）Mo的放射化学产率>80%，产物纯度符合国际药典标准。
